ANALYSIS OF SELF-SHUTDOWN BEHAVIOR IN THE SPERT I REACTOR (open access)

ANALYSIS OF SELF-SHUTDOWN BEHAVIOR IN THE SPERT I REACTOR

Presented at the 1958 Winter Meeting of the American Nuclear Society, December 9, 1958. Experimental and theoretical work on the selflimiting response of reactors to step and ramp insertions of reactivity is discussed along with the general characteristics of self-limiting power bursts. The static characteristics of the cores investigated are presented and the techniques of measurement are discussed. Data from step and ramp tests are presented and compared with the predictions of a theoretical formulation of reactor self- shutdown in terms of energy release. The discussion includes an evaluation of some postulated shutdown mechanisms in the light of experimental results. Some results of detailed calculations of shutdown effects due to specific mechanisms which are believed to contribute significantly to reactor self-shutdown are presented. (auth)
Date: July 23, 1959
Creator: Forbes, S. G.; Bentzen, F. L.; French, P.; Grund, J. E.; Haire, J. C.; Nyer, W. E. et al.
Object Type: Report
System: The UNT Digital Library
DECONTAMINATION OF THE PRFR PILOT LEACHING PLANT--PRELIMINARY PROCESS DESIGN (open access)

DECONTAMINATION OF THE PRFR PILOT LEACHING PLANT--PRELIMINARY PROCESS DESIGN

The Turco 4501 process is recommended for the decontamination of the PRFR pilot leaching plant equipment. The caustic-tartrate-nitric acid process is recommended for the decontamination of the cell and the equipment exterior. (auth)
Date: July 23, 1959
Creator: McLain, H. A.
Object Type: Report
System: The UNT Digital Library
Decontamination of the PRFR Pilot Leaching Plant - Preliminary Process Design (open access)

Decontamination of the PRFR Pilot Leaching Plant - Preliminary Process Design

The Turco 4501 process is recommended for the decontamination of the PRFR pilot leaching plant equipment. The caustic-tartrate-nitric acid process is recommended for the decontamination of the cell and the equipment exterior.
Date: July 23, 1959
Creator: McLain, H. A.
Object Type: Report
System: The UNT Digital Library
Determination of the Nil-Ductility-Transition Temperature for A212B Steel Used in the N. S. Savannah Pressure Vessel (open access)

Determination of the Nil-Ductility-Transition Temperature for A212B Steel Used in the N. S. Savannah Pressure Vessel

The nil-ductility-transition (NDT) temperature, as defined by the Naval Research Laboratory drop-weight test, was determined on the A212B carbon-silicon steel used in the pressure vessel of the N. S. Savannah nuclear reactor. Correlations were made with the Charpy-V-notch impact energy at NDT. Specimens taken at two different thickness location from materials used in the upper closure head of the reactor vessel yielded NDT temperatures of 0 - 20°F which correspond to Charpy-V-notch impact energies of 11-19 ft-lb. Testing of as-received material used in the lower closure head indicated that the NDT temperature was 50°F which was equivalent to an average Charpy-V-notch impact energy of 12 ft-lb. After normalizing and stress-relieving this material, in order to more closely approximate the final condition of the reactor vessel, NDT was reduced to less than 10°F.
Date: July 23, 1959
Creator: Thurber, W. C. & Lamartine, J. T.
Object Type: Report
System: The UNT Digital Library
DETERMINATION OF THE NIL-DUCTILITY-TRANSITION TEMPERATURE FOR A212B STEEL USED IN THE N.S. SAVANNAH PRESSURE VESSEL (open access)

DETERMINATION OF THE NIL-DUCTILITY-TRANSITION TEMPERATURE FOR A212B STEEL USED IN THE N.S. SAVANNAH PRESSURE VESSEL

The nil-ductility-transitaion (NDT) temperature, as defined by the Naval Research Laboratory drop-weight test, was determined on the A212B carbon-silicon steel used in the pressure vessel of the N. S. Savannah reactor. Correlations were made with the Charpy-V-notch impact energy at NDT. Specimens taken at two different thickness locations from material used in the ipper closure head of the reactor vessel yielded NDT temperatures of 0 to 20 deg F which correspond to Charpy-V-notch impact energies of 11 to 19 ft-lb. Testing of as-received material used in the lower closure head indicated that the NDT temperature was 50 deg F which was equivalent to an average CharpyV-notch impact energy of 12 ft-lb. After normalizing and stress-relieving thin material, in order to more closely approximate the final ccndition of the reactor vessel, NDT was reduced to less than 10 deg F. (auth)
Date: July 23, 1959
Creator: Thurber, W.C. & Lamartine, J.T.
Object Type: Report
System: The UNT Digital Library
Prfr Pilot Leaching Plant-Preliminary Process Design (open access)

Prfr Pilot Leaching Plant-Preliminary Process Design

The preliminary process design of a PRFR pilot leaching plant, the proposed location of which is in Cell B of Building 3026 at ORNL, is considered. Chemical, physical, and nuclear parameters are investigated to assure safe leaching operations. Nitric acid solvents are used for leaching the uranium and/ or thorium from the sheared spent fuel elements, and the dissolved fuel is sent through a shielded pipeline to the extraction plant for further processing. Recommended materials of construction are 304L stainless steel and 3O9SCb stainless steel, and maintenance is by direct procedures. (auth)
Date: July 23, 1959
Creator: McLain, H. A.
Object Type: Report
System: The UNT Digital Library
PRFR  Pilot Leaching Plant - Preliminary Process Design (open access)

PRFR Pilot Leaching Plant - Preliminary Process Design

The preliminary process design of a PRFR pilot leaching plant, which is proposed to be located in Cell B of Building ORNL, is considered. Chemical, physical, and nuclear parameters are investigated in order that the leaching operations may be carried out without any chemical or nuclear hazards.
Date: July 23, 1959
Creator: McLain, H. A.
Object Type: Report
System: The UNT Digital Library
Texas Attorney General Opinion: WW-671 (open access)

Texas Attorney General Opinion: WW-671

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Questions relating to issuance of salary warrants to the President of Texas Southern University.
Date: July 23, 1959
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History